ML20138G919
| ML20138G919 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/18/1985 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20138G911 | List: |
| References | |
| GL-83-43, NUDOCS 8510280088 | |
| Download: ML20138G919 (5) | |
Text
Enclosure 1 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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GENERAL PUBLIC UTILITIES NUCLEAR
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Docket No. 50-320 CORPORATION
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(Three Mile Island Nuclear Station, )
Unit 2)
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AMENDMENT OF ORDER I.
GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the licensee) are the holders of Facility Operating License No. DPR-73, which had authorized operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2) at power levels up to 2772 megawatts thermal. The facility, which is located in Londonderry Township, Dauphin County, Pennsylvania, is a pressurized water reactor previously used for the commercial generation of electricity.
II.
By Order for Modification of License, dated July 20, 1979, the licensee's authority to operate the facility was suspended and the licensee's authority was limited to maintenance of the facility in the present shut-down cooling mode (44 Fed. Reg. 45271). By further Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of formal license re,uirements was imposed to reflect the post-accident condition of the facility and to assure the continued maintenance of the current safe, stable, long-term cooling condition of the facility (45 Fed.
Reg. 11292).
8510280000 851010 PDR ADOCK 05000320 p
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Although these requirements were imposed on the licensee by an Order of the Director of Nuclear Reactor Regulation, dated February 11, 1980, the Tlil-2 license has not been formally amended. The requirements are reflected in the Recovery Mode Proposed Technical Specifications (PTS) presently pending before the Atomic Safety and Licensing Board. The revir,lons that are the I
subject of this order do not give the licensee authorizations that may be needed to undertake specific cleanup activities. Hereafter in this Amend-ment of Order, the requirements in question are identified by the applicable Proposed Technical Specification.
III.
By letters dated April 12, 1985 and June 18, 1985, GPU Nuclear Corporation (GPUNC) requested that the PTS be modified. The requests consisted of changes to the PTS to confom with the requirements contained in the NRC Generic Letter 83-43, Reporting Requirements of 10 CFR Part 50, Sections 50.72 and 50.73, and the Standard Technical Specifications. Other changes requested by the licensee deleted requirements for equipment and monitoring that are no longer needed and proposed administrative and editorial changes to improve clarity. The licensee also requested that reference to the Programatic Environmental Impact Statement be dropped from the defir.ition of " review significant" as defined in PTS 1.14. The licensee is currently required to make a determination as to whether or not documents implementing the cleanup or submitted to the NRC are bounded by the PEIS.
In particular, the licensee has proposed changes to PTS 1.6, 3.0.3, 3.3.3.8,3.4.2,3.7.10.1,3.7.10.2,3.7.10.3,6.5.2.5(d)and(e),6.6,6.9, 6.9.1.7, 6.9.1.8, 6.9.1.9, and 6.10.2(c), to conform to the provisions l
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i 1.14, 3.4.9.1, 6.5.2.3, of 10 CFR $50.72 or 50.73, as appropriate; to PTS 6.5.2.5.a. 6.5.3.1, 6.9.1, and 6.9.2, to correct typographical errors or to clarify existing provisions or otherwise achieve consistency, without affecting the substance of the existing requirements; and to PTS 3.6.4 a 3.7.10.2, to delete requirements which are no longer necessary given the current status of the plant.
12, 1985 and After reviewing the licensee's safety evaluations in the April letters and performing its own safety evaluation, the staff June 18, 1985 has concluded, with the exception noted below, that the requested changes are acceptable and has modified the appropriate sections of the The staff has determined that it is not appropriate to delete the PTS.
PEIS as a document used to determine review significance; however, for those activities that are clearly within the scopo of an NRC approved f
system description SER or TER, no additional comparison to PEI The text of the definition for " review significant" has been required.
changed accordingly.
4 The staff's safety assessment of this matter as discussed above is set Since the February 11, forth in the concurrently issued Safety Evaluation.
1980 Order imposing the Proposed Technical Specifications is curren pending before the Atomic Safety and Licensing Board, the staff w advising the Licensing Board of this Amendment of Order through l
Issuance of Amendment of Order and a Motion to Conform Propo 4
Specifications in Accordance Herewith.
This action involves changes to requirements with respect to the installation or use of a facility component located within the restricted area, as well as changes in recordkeeping, reporting or administrative procedures or requirements. The staff has determined that this action involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. Accordingly, this action meets the eligibility e-iteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this action.
IV.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, the Director's Order of February 11, 1980, is hereby revised to incorporate the deletions, additions, and modifications set forth in Enclosure 3 hereto.
This Amendment of Order shall be effective on November 22, 1985.
Forfurtherdetailswithrespecttothisaction,see(1)LettertoB.J.
Snyder, USNRC, from F. R. Standerfer, GPUNC, Technical Specification Change Request 48 and Recovery Operations Plan Change Request 29, dated April 12, 1985, (2) Letter to B. J. Snyder, USNRC, from F. R. Standerfer, GPUNC, Technical Specification Change Request No. 50 and Recovery Operations Plan Change Request No. 32, dated June 18, 1985, and (3) the Director's Order of February 11, 1980.
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All the above documents are available for inspection at the Comission's Public Document Room, 1717 H Street, N.W., Washington, DC 20555, and at the Comission's Local Public Document Room at the State Library of Pennsylvania, Government Publications Section, Education Building Comon-wealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
FOR THE NUCLEAR REGULATORY COM ISSION rre 1
. E se hut, Deputy Director Office of Nuclear Reactor Regulation Effective Date: November 22, 1985 Dated at Bethesda, Maryland Issuance Date: October 18, 1985 l
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